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| | document type = Memoranda, Request for Additional Information (RAI) | | | document type = Memoranda, Request for Additional Information (RAI) |
| | page count = 4 | | | page count = 4 |
| | project = TAC:ME8536, TAC:ME8535 | | | project = TAC:ME8535, TAC:ME8536 |
| | stage = Draft RAI | | | stage = Draft RAI |
| }} | | }} |
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| =Text= | | =Text= |
| {{#Wiki_filter: August 22, 2012 MEMORANDUM TO: Meena K. Khanna, Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: Richard B. Ennis, Senior Project Manager /RA/ Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation | | {{#Wiki_filter:August 22, 2012 MEMORANDUM TO: Meena K. Khanna, Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: Richard B. Ennis, Senior Project Manager /RA/ Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation |
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| ==SUBJECT:== | | ==SUBJECT:== |
| PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3, DRAFT REQUEST FOR ADDITIONAL INFORMATION (TAC NOS. ME8535 AND ME8536) The attached draft request for additional information (RAI) was transmitted on August 22, 2012, to Mr. Thomas Loomis of Exelon Generation Company, LLC (Exelon, the licensee). This information was transmitted to facilitate an upcoming conference call in order to clarify the licensee=s amendment request for Peach Bottom Atomic Power Station (PBAPS), Units 2 and 3, dated April 27, 2012. The proposed amendment would: (1) adopt a new methodology for preparation of the reactor coolant system pressure-temperature (P-T) limits; (2) relocate the P-T limits in the technical specifications (TSs) to a new licensee-controlled document, the Pressure and Temperature Limits Report (PTLR); and (3) modify the TSs to add references to the PTLR. PBAPS, Units 2 and 3, are currently licensed to P-T limits that are applicable up to 32 effective full power years (EFPY). The PTLR would include P-T limits applicable to both 32 EFPY and 54 EFPY. | | PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3, DRAFT REQUEST FOR ADDITIONAL INFORMATION (TAC NOS. ME8535 AND ME8536) |
| The draft RAI was sent to Exelon to ensure that the questions are understandable, the regulatory basis for the questions is clear, and to determine if the information was previously docketed. This memorandum and the attachment do not convey or represent an NRC staff position regarding the licensee's request. | | The attached draft request for additional information (RAI) was transmitted on August 22, 2012, to Mr. Thomas Loomis of Exelon Generation Company, LLC (Exelon, the licensee). This information was transmitted to facilitate an upcoming conference call in order to clarify the |
| Docket Nos. 50-277 and 50-278 | | |
| | licensee=s amendment request for Peach Bottom Atomic Power Station (PBAPS), Units 2 and 3, dated April 27, 2012. The proposed amendment would: (1) adopt a new methodology for preparation of the reactor coolant system pressure-temperature (P-T) limits; (2) relocate the P-T limits in the technical specifications (TSs) to a new licensee-controlled document, the Pressure and Temperature Limits Report (PTLR); and (3) modify the TSs to add references to the PTLR. PBAPS, Units 2 and 3, are currently licensed to P-T limits that are applicable up to 32 effective full power years (EFPY). The PTLR would include P-T limits applicable to both 32 EFPY and 54 EFPY. |
| | The draft RAI was sent to Exelon to ensure that the questions are understandable, the regulatory basis for the questions is clear, and to determine if the information was previously docketed. This memorandum and the attachment do not convey or represent an NRC staff position regarding the licensee's request. |
| | |
| | Docket Nos. 50-277 and 50-278 |
|
| |
|
| ==Attachment:== | | ==Attachment:== |
| Draft RAI August 22, 2012 MEMORANDUM TO: Meena K. Khanna, Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: Richard B. Ennis, Senior Project Manager /RA/ Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation | | Draft RAI |
| | |
| | August 22, 2012 MEMORANDUM TO: Meena K. Khanna, Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: Richard B. Ennis, Senior Project Manager /RA/ Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation |
|
| |
|
| ==SUBJECT:== | | ==SUBJECT:== |
| PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3, DRAFT REQUEST FOR ADDITIONAL INFORMATION (TAC NOS. ME8535 AND ME8536) The attached draft request for additional information (RAI) was transmitted on August 22, 2012, to Mr. Thomas Loomis of Exelon Generation Company, LLC (Exelon, the licensee). This information was transmitted to facilitate an upcoming conference call in order to clarify the licensee=s amendment request for Peach Bottom Atomic Power Station (PBAPS), Units 2 and 3, dated April 27, 2012. The proposed amendment would: (1) adopt a new methodology for preparation of the reactor coolant system pressure-temperature (P-T) limits; (2) relocate the P-T limits in the technical specifications (TSs) to a new licensee-controlled document, the Pressure and Temperature Limits Report (PTLR); and (3) modify the TSs to add references to the PTLR. | | PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3, DRAFT REQUEST FOR ADDITIONAL INFORMATION (TAC NOS. ME8535 AND ME8536) |
| PBAPS, Units 2 and 3, are currently licensed to P-T limits that are applicable up to 32 effective full power years (EFPY). The PTLR would include P-T limits applicable to both 32 EFPY and 54 EFPY. The draft RAI was sent to Exelon to ensure that the questions are understandable, the regulatory basis for the questions is clear, and to determine if the information was previously docketed. This memorandum and the attachment do not convey or represent an NRC staff position regarding the licensee's request. Docket Nos. 50-277 and 50-278 | | The attached draft request for additional information (RAI) was transmitted on August 22, 2012, to Mr. Thomas Loomis of Exelon Generation Company, LLC (Exelon, the licensee). This information was transmitted to facilitate an upcoming conference call in order to clarify the licensee=s amendment request for Peach Bottom Atomic Power Station (PBAPS), Units 2 and 3, dated April 27, 2012. The proposed amendment would: (1) adopt a new methodology for preparation of the reactor coolant system pressure-temperature (P-T) limits; (2) relocate the P-T limits in the technical specifications (TSs) to a new licensee-controlled document, the Pressure and Temperature Limits Report (PTLR); and (3) modify the TSs to add references to the PTLR. |
| | PBAPS, Units 2 and 3, are currently licensed to P-T limits that are applicable up to 32 effective full power years (EFPY). The PTLR would include P-T limits applicable to both 32 EFPY and 54 EFPY. The draft RAI was sent to Exelon to ensure that the questions are understandable, the regulatory basis for the questions is clear, and to determine if the information was previously docketed. This memorandum and the attachment do not convey or represent an NRC staff position regarding the licensee's request. |
| | Docket Nos. 50-277 and 50-278 |
|
| |
|
| ==Attachment:== | | ==Attachment:== |
| Draft RAI DISTRIBUTION PUBLIC DWidrevitz, NRR/EVIB LPL1-2 R/F BParks, NRR/SRXB RidsNrrDorlLpl1-2 Resource RidsNrrDorlDpr Resource RidsNrrPMPeachBottom Resource ACCESSION NO.: ML12236A154 OFFICE LPL1-2/PM NAME REnnis DATE 8/22/12 OFFICIAL RECORD COPY DRAFT REQUEST FOR ADDITIONAL INFORMATION REGARDING PROPOSED LICENSE AMENDMENT RELOCATION OF PRESSURE AND TEMPERATURE LIMIT CURVES TO THE PRESSURE AND TEMPERATURE LIMITS REPORT PEACH BOTTOM ATOMIC POWER STATION - UNITS 2 AND 3 DOCKET NOS. 50-277 AND 50-278 By letter to the Nuclear Regulatory Commission (NRC) dated April 27, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML121230354), Exelon Generation Company, LLC (Exelon, the licensee), submitted a license amendment request for Peach Bottom Atomic Power Station (PBAPS), Units 2 and 3. The proposed amendment would: (1) adopt a new methodology for preparation of the reactor coolant system pressure-temperature (P-T) limits; (2) relocate the P-T limits in the technical specifications (TSs) to a new licensee-controlled document, the Pressure and Temperature Limits Report (PTLR); and (3) modify the TSs to add references to the PTLR. PBAPS, Units 2 and 3, are currently licensed to P-T limits that are applicable up to 32 effective full power years (EFPY). The PTLR would include P-T limits applicable to both 32 EFPY and 54 EFPY. | | Draft RAI |
| The NRC staff has reviewed the information the licensee provided that supports the proposed amendment and would like to discuss the following issues to clarify the submittal. 1. Section 1.0 of Attachment 1 to the licensee's application dated April 27, 2012, states that relocation of the P-T limit curves to the PTLR is consistent with the guidance provided in NRC-approved GE Hitachi Nuclear Energy Licensing Topical Report NEDC-33178P-A, Revision 1 (ADAMS Accession No. ML092370486). Equations 4-2 and 4-3 in Section 4.3.2.1.1 of NEDC-33178P-A are used to determine if the generic Pressure Test - Non-Beltline, Curve A is applicable. The equations are as follows: R / t1/2 = 138 / 81/2 = 49 inch1/2 Equation 4-2 R / t1/2 Equation 4-3 As discussed in Section 4.3.2.1.1 of NEDC-33178P-A, if the plant-specific result of Equation 4-3 is greater than that of the generic value from Equation 4-2, the user is directed to perform a plant-specific evaluation. The NRC staff conducted the comparison and found that the PBAPS-provided geometry information results in a value greater than the generic value. Justify the use of the Section 4.3.2.1.1 curve or submit a plant-specific evaluation. 2. 10 CFR Part 50, Appendix G, Paragraph IV.A states that, "the pressure-retaining components of the reactor coolant pressure boundary [RCPB] that are made of ferritic materials must meet the requirements of the [American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code], supplemented by the additional requirements Attachment set forth below." These requirements include paragraph IV.A.2, "Pressure-Temperature Limits and Minimum Temperature Requirements". Therefore, 10 CFR Part 50, Appendix G requires that P-T limits be developed for the ferritic materials in the reactor vessel (RV) beltline (neutron fluence 1 x 1017 n/cm2, E > 1 MeV), as well as ferritic materials not in the RV beltline (neutron fluence < 1 x 1017 n/cm2, E > 1 MeV). Further, 10 CFR Part 50, Appendix G requires that all RCPB components must meet the ASME Code, Section III requirements. The relevant ASME Code, Section III requirement that will affect the P-T limits is the lowest service temperature requirement for all RCPB components specified in Section III, NB-2332(b). The P-T limit calculations for ferritic RCPB components that are not RV beltline shell materials may define P-T curves that are more limiting than those calculated for the RV beltline shell materials due to the following factors: a) RV nozzles, penetrations, and other discontinuities have complex geometries that may exhibit significantly higher stresses than those for the RV beltline shell region. These higher stresses can potentially result in more restrictive P-T limits, even if the reference temperature (RTNDT) for these components is not as high as that of RV beltline shell materials that have simpler geometries. b) Ferritic RCPB components that are not part of the RV may have initial RTNDT values, which may define a more restrictive lowest operating temperature in the P -T limits than those for the RV beltline shell materials. Consequently, please describe how the P-T limit curves submitted for PBAPS, Units 2 and 3 and the methodology used to develop these curves, considered all RV materials (beltline and non-beltline) and the lowest service temperature of all ferritic RCPB materials, consistent with the requirements of 10 CFR Part 50, Appendix G. | | |
| }} | | DISTRIBUTION PUBLIC DWidrevitz, NRR/EVIB LPL1-2 R/F BParks, NRR/SRXB RidsNrrDorlLpl1-2 Resource RidsNrrDorlDpr Resource RidsNrrPMPeachBottom Resource ACCESSION NO.: ML12236A154 OFFICE LPL1-2/PM NAME REnnis DATE 8/22/12 OFFICIAL RECORD COPY DRAFT REQUEST FOR ADDITIONAL INFORMATION REGARDING PROPOSED LICENSE AMENDMENT RELOCATION OF PRESSURE AND TEMPERATURE LIMIT CURVES TO THE PRESSURE AND TEMPERATURE LIMITS REPORT PEACH BOTTOM ATOMIC POWER STATION - UNITS 2 AND 3 DOCKET NOS. 50-277 AND 50-278 By letter to the Nuclear Regulatory Commission (NRC) dated April 27, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML121230354), Exelon Generation Company, LLC (Exelon, the licensee), submitted a license amendment request for Peach Bottom Atomic Power Station (PBAPS), Units 2 and 3. The proposed amendment would: (1) adopt a new methodology for preparation of the reactor coolant system pressure-temperature (P-T) limits; (2) relocate the P-T limits in the technical specifications (TSs) to a new licensee-controlled document, the Pressure and Temperature Limits Report (PTLR); and (3) modify the TSs to add references to the PTLR. PBAPS, Units 2 and 3, are currently licensed to P-T limits that are applicable up to 32 effective full power years (EFPY). The PTLR would include P-T limits applicable to both 32 EFPY and 54 EFPY. |
| | |
| | The NRC staff has reviewed the information the licensee provided that supports the proposed amendment and would like to discuss the following issues to clarify the submittal. |
| | : 1. Section 1.0 of Attachment 1 to the licensee's application dated April 27, 2012, states that relocation of the P-T limit curves to the PTLR is consistent with the guidance provided in NRC-approved GE Hitachi Nuclear Energy Licensing Topical Report NEDC-33178P-A, Revision 1 (ADAMS Accession No. ML092370486). Equations 4-2 and 4-3 in Section 4.3.2.1.1 of NEDC-33178P-A are used to determine if the generic Pressure Test - Non-Beltline, Curve A is applicable. The equations are as follows: |
| | R / t 1/2 = 138 / 8 1/2 = 49 inch 1/2 Equation 4-2 |
| | |
| | R / t 1/2 Equation 4-3 As discussed in Section 4.3.2.1.1 of NEDC-33178P-A, if the plant-specific result of Equation 4-3 is greater than that of the generic value from Equation 4-2, the user is directed to perform a plant-specific evaluation. The NRC staff conducted the comparison and found that the PBAPS-provided geometry information results in a value greater than the generic value. Justify the use of the Section 4.3.2.1.1 curve or submit a plant-specific evaluation. |
| | : 2. 10 CFR Part 50, Appendix G, Paragraph IV.A states that, "the pressure-retaining components of the reactor coolant pressure boundary [RCPB] that are made of ferritic materials must meet the requirements of the [American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code], supplemented by the additional requirements |
| | |
| | Attachment set forth below." These requirements include paragraph IV.A.2, "Pressure-Temperature Limits and Minimum Temperature Requirements". Therefore, 10 CFR Part 50, Appendix G requires that P-T limits be developed for the ferritic materials in the reactor vessel (RV) beltline (neutron fluence 1 x 10 17 n/cm 2, E > 1 MeV), as well as ferritic materials not in the RV beltline (neutron fluence < 1 x 10 17 n/cm 2, E > 1 MeV). Further, 10 CFR Part 50, Appendix G requires that all RCPB components must meet the ASME Code, Section III requirements. The relevant ASME Code, Section III requirement that will affect the P-T limits is the lowest service temperature requirement for all RCPB components specified in Section III, NB-2332(b). |
| | The P-T limit calculations for ferritic RCPB components that are not RV beltline shell materials may define P-T curves that are more limiting than those calculated for the RV beltline shell materials due to the following factors: |
| | a) RV nozzles, penetrations, and other discontinuities have complex geometries that may exhibit significantly higher stresses than those for the RV beltline shell region. These higher stresses can potentially result in more restrictive P-T limits, even if the reference temperature (RT NDT) for these components is not as high as that of RV beltline shell materials that have simpler geometries. |
| | b) Ferritic RCPB components that are not part of the RV may have initial RTNDT values, which may define a more restrictive lowest operating temperature in the P -T limits than those for the RV beltline shell materials. |
| | Consequently, please describe how the P-T limit curves submitted for PBAPS, Units 2 and 3 and the methodology used to develop these curves, considered all RV materials (beltline and non-beltline) and the lowest service temperature of all ferritic RCPB materials, consistent with the requirements of 10 CFR Part 50, Appendix G.}} |
Letter Sequence Draft RAI |
|---|
TAC:ME8535, Revise PTLR Definition and References in ISTS 5.6.6, RCS PTLR, Revise Topical Report References in ITS 5.6.5, Colr, Relocation of Ltop Enabletemperature and PORV Lift Setting to the PTLR - CE NPSD-683 (Approved, Closed) TAC:ME8536, Revise PTLR Definition and References in ISTS 5.6.6, RCS PTLR, Revise Topical Report References in ITS 5.6.5, Colr, Relocation of Ltop Enabletemperature and PORV Lift Setting to the PTLR - CE NPSD-683 (Approved, Closed) |
|
MONTHYEARML1212303542012-04-27027 April 2012
License Amendment Request - Relocation of Pressure and Temperature Limit Curves to the Pressure and Temperature Limits Report
Project stage: Request
ML1215000382012-05-29029 May 2012
Acceptance Review for TACs ME8535 and ME8536 - Peach Bottom Units 2 and 3 - Relocation of P-T Limits to PTLR
Project stage: Acceptance Review
ML1212905292012-06-0101 June 2012
Request for Withholding Information from Public Disclosure for Peach Bottom Atomic Power Station, Unit Nos. 2 and 3
Project stage: Withholding Request Acceptance
ML1212905172012-06-0101 June 2012
Request for Withholding Information from Public Disclosure for Peach Bottom Atomic Power Station, Unit Nos. 2 and 3
Project stage: Withholding Request Acceptance
ML12236A1542012-08-22022 August 2012
Draft Request for Additional Information
Project stage: Draft RAI
ML12290A1132012-10-15015 October 2012
Response to Request for Additional Information - License Amendment Request for Relocation of Pressure and Temperature Limit Curves to the Pressure and Temperature Limits Report
Project stage: Response to RAI
ML12300A0422012-11-13013 November 2012
Request for Withholding Information from Public Disclosure for
Project stage: Withholding Request Acceptance
ML13079A1902013-03-22022 March 2013
Transmittal of Draft Safety Evaluation for Proposed Amendment Relocation of Pressure and Temperature Limit Curves to the Pressure and Temperature Limits Report
Project stage: Draft Approval
ML13079A2192013-04-0101 April 2013
Issuance of Amendments Relocation of Pressure and Temperature Limit Curves to the Pressure and Temperature Limits Report
Project stage: Approval
2012-05-29
[Table View] |
|
|---|
Category:Memoranda
MONTHYEARML23276A6522023-10-11011 October 2023
Pre-submittal Meeting Summary, September 14, 2023
CLI-22-04, Change Letter to Peach Bottom Subsequent Renewed Licenses March 17 2022 Rev 12022-03-25025 March 2022
Change Letter to Peach Bottom Subsequent Renewed Licenses_March 17 2022_Rev 1
ML21309A5482021-11-15015 November 2021
NSIR Staff Review of the Wolf Creek Generating Stations Security Plan Training & Qualification Plan & Safeguards Contingency Plan for the Verification of ASM EA 20 091 Incorporation
ML21277A2472021-11-0505 November 2021
Notification of Significant Licensing Action - Proposed Issuance of Order Approving the Transfer of Licenses for Which a Hearing Has Been Requested - Exelon Generation Company, LLC; Et. Al
ML21243A4492021-09-0202 September 2021
ISFSI Technical Assistance Request - Review of Physical Security Plan
ML20296A3342020-10-21021 October 2020
ISI Remote Inspection - Supplemental Request for Information
ML19088A0462019-03-26026 March 2019
Submittal of 2018 Occupational Exposure Report (1O CFR 20.2206(b)
ML18288A1942018-10-25025 October 2018
Summary of the Site Visit Related to the Review of the Subsequent License Renewal Application for the Peach Bottom Atomic Power Station Units 2 and 3
ML18151A1632018-06-0404 June 2018
Summary of Peach Bottom Annual Assessment Meeting and Attendee List
ML18100A2112018-04-26026 April 2018
Notice of Public Meeting May 24, 2018
ML18044A1632018-02-20020 February 2018
01/18/2018 Summary of Pre-Application Meeting with Exelon Corporation Regarding the Peach Bottom, Units 2 and 3, Subsequent License Renewal Application
ML17271A0532017-09-29029 September 2017
2017 Summary of Annual Decommissioning Funding Status Reports for Reactors in Decommissioning
ML17142A2382017-05-25025 May 2017
OEDO-17-00280 - Briefing Package for Drop-In Visit on June 9, 2017, by Senior Management of Exelon Generation Company, LLC with Chairman Svinicki, Commissioner Baran, and Commissioner Burns
ML17090A1282017-04-0505 April 2017
Notice of Public Meeting with Exelon Generation Company, LLC to Discuss Nrc'S Assessment of Safety Performance at Peach Bottom Atomic Power Station for 2016
ML16221A6802016-08-0808 August 2016
Draft Request for Additional Information
ML16209A2042016-07-27027 July 2016
Draft Request for Additional Information
ML16088A2052016-03-28028 March 2016
Enclosure 1 - (72.30 DFP Reviews to Be Completed 2015) - Memo T Bowers from s Ruffin, Technial Assistance Requests - Review 2015 Tri-Annual Decommissioning Funding Plans for Multiple Independent Spent Fuel Storage Installations
ML16088A2042016-03-28028 March 2016
Memo T Bowers from s Ruffin, Technical Assistance Requests - Review 2015 Tri-Annual Decommissioning Funding Plans for Multiple Independent Spent Fuel Storage Installations W/ Encl 2 (Template)
ML16075A3292016-03-16016 March 2016
OEDO-16-00165 - Briefing Package for Drop-In Visit on March 23, 2016, by Senior Management of Exelon Generation Company, LLC with the NRC Executive Director for Operations
ML16056A5632016-02-25025 February 2016
Draft Request for Additional Information
ML15253A5802015-09-0909 September 2015
Draft Request for Additional Information
ML15223A5152015-08-10010 August 2015
Draft Request for Additional Information
ML15205A3562015-07-24024 July 2015
Draft Request for Additional Information
ML15127A2472015-05-0606 May 2015
Draft Request for Additional Information
ML15127A5182015-05-0505 May 2015
Draft Request for Additional Information (Tac No. MF4792)
ML15110A0602015-04-17017 April 2015
Draft Request for Additional Information
ML15098A0392015-04-0808 April 2015
Draft Request for Additional Information
ML15078A0832015-03-19019 March 2015
Draft Request for Additional Information (TAC Nos. MF5172 and MF5173)
ML15077A2742015-03-18018 March 2015
March 26, 2015, Forthcoming Closed Meeting with Exelon Generation Company, LLC, (Exelon) to Discuss Steam Dryer Analysis Methodology Change for Peach Bottom Atomic Power Station (Pbaps), Unit 2
ML15056A0462015-02-24024 February 2015
Draft Request for Additional Information
ML14349A7072014-12-12012 December 2014
Draft Request for Additional Information
ML14309A7732014-11-0404 November 2014
Draft Request for Additional Information
ML14133A0592014-07-0101 July 2014
Summary of Closed Meeting Between Representatives of the Army Corps of Engineers, Nuclear Regulatory Commission, Federal Energy Regulatory Commission, Exelon Generation Co, LLC, and PPL Susquehanna, LLC, to Discuss Dam Failure Analysis..
ML14112A2392014-04-22022 April 2014
Notice of Forthcoming Closed Meeting to Discuss Dam Failure Analysis for Peach Bottom Atomic Power Station Units 2 and 3, Susquehanna Steam Electric Station Units 1 and 2, and Three Mile Island Nuclear Station Unit 1
ML14063A3862014-03-0606 March 2014
Notice of Forthcoming Closed Meeting with Exelon Generation Company, LLC (Exelon) to Discuss Steam Dryer Analysis Related to Proposed Extended Power Uprate (EPU) for Peach Bottom Atomic Power Station (Pbaps), Unit Nos. 2 and 3
ML14056A1152014-02-24024 February 2014
Draft Request for Additional Information
ML13309A0802013-12-11011 December 2013
Memorandum to File: Transcript for 10 CFR 2.206 Petition from Beyond Nuclear (Et Al) Regarding General Electric Mark I and Mark II Boiling-Water Reactors
ML13338A2502013-12-0404 December 2013
Notice of Forthcoming Closed Meeting with Exelon Generation Company, LLC (Exelon) to Discuss Steam Dryer Analysis Related to Proposed Extended Power Uprate (EPU) for Peach Bottom Atomic Power Station (Pbaps), Units 2 and 3
ML13261A1572013-09-17017 September 2013
Draft Request for Additional Information
ML13190A3522013-07-10010 July 2013
Notice of Forthcoming Teleconference with Exelon Generation Company, LLC
ML13154A2762013-03-0606 March 2013
NRC Comments on Draft Licensee-Developed Exam (Operating) (Folder 2)
ML13063A3372013-03-0404 March 2013
Draft Request for Additional Information
ML12348A6962012-12-17017 December 2012
1/3/2013 - Notice of Forthcoming Meeting with Exelon Generation Company, LLC, to Discuss Requests for Additional Information Regarding Exelon Physical Security Plans
ML12310A4882012-11-0505 November 2012
Draft Request for Additional Information
ML12236A1542012-08-22022 August 2012
Draft Request for Additional Information
ML12194A6082012-07-12012 July 2012
Draft Request for Additional Information
ML12137A1792012-05-17017 May 2012
Forthcoming Pre-submittal Public Meeting with Exelon Generation Company, LLC Regarding LaSalle Extended Power Uprate Replacement Steam Dryer
ML1208602902012-03-26026 March 2012
Notice of Forthcoming Public Meeting with Exelon Generation to Discuss Future Fleet Submittal Regarding Licensed Operator Eligibility Requirements
ML1206600702012-03-0606 March 2012
02/21-22/2012 Meeting Summary with State-Of-The-Art Reactor Consequence Analyses (Soarca) for Public Meetings at Peach Bottom and Surry
ML11250A1712011-09-14014 September 2011
Notice of Forthcoming Meeting with Petitioner Requesting Action Under 10 CFR 2.206 Regarding Immediate Suspension of the Operating Licenses of General Electric (GE) Mark 1 Boiling Water Reactors (Bwrs)
2023-10-11
[Table view]
Category:Request for Additional Information (RAI)
MONTHYEARML24197A0162024-07-12012 July 2024
NRR E-mail Capture - Final RAI - Constellation Energy Generation, LLC - Fleet Request - License Amendment Request to Adopt TSTF-591
ML24185A1772024-07-0303 July 2024
Request for Additional Information
ML23264A7992023-09-21021 September 2023
NRR E-mail Capture - Final RAI - Constellation Energy Generation, LLC Fleet Request License Amendment Request to Adopt TSTF-580, Revision 1
ML22118A3312022-04-28028 April 2022
NRR E-mail Capture - Peach Bottom - Formal RAI for Proposed Alternative I5R-14, Revision 1
ML22041B5362022-02-10010 February 2022
NRR E-mail Capture - Constellation Energy Generation, LLC - Request for Additional Information Regarding Fleet License Amendment Request to Adopt TSTF-541
ML22021A5692022-01-21021 January 2022
Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection 05000277/2022403 and 05000278/2022403
ML22020A0642022-01-13013 January 2022
NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Proposed Fleet Alternative for Repair of Water Level Instrumentation Partial Penetration Nozzles
ML21256A1902021-09-10010 September 2021
NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application
ML21144A2132021-05-24024 May 2021
NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application
ML21062A0652021-03-0101 March 2021
NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Proposed Fleet Alternative to Documentation Requirements for Pressure Retaining Bolting
ML21049A2572021-02-18018 February 2021
Request for Additional Information Byron/Dresden Proposed Changes to Site Emergency Plans to Support Post-Shutdown and Permanently Defueled Conditions (EPID-2020-LLA-0240 & EPID-2020-LLA-0237)
ML21035A2222021-02-0404 February 2021
Notification of Conduct of a Fire Protection Team Inspection
ML21091A1782021-02-0202 February 2021
Ti 2515/194 Inspection Documentation Request
ML21012A1302021-01-12012 January 2021
Request for Additional Information - TSTF-505
ML20357A0972020-12-21021 December 2020
Request for Additional Information - TSTF-505
ML20296A3342020-10-21021 October 2020
ISI Remote Inspection - Supplemental Request for Information
ML20239A7982020-08-25025 August 2020
NRR E-mail Capture - Exelon Generation Company, LLC - Fleet License Amendment Request to Adopt TSTF-568, Revision 2
ML20153A7042020-06-0101 June 2020
NRR E-mail Capture - Preliminary RAI for Fleet Request to Use Alternative OMN-26
ML20135H1972020-05-14014 May 2020
NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Request to Extend Safety Relief Valve Test Interval
ML20070R2282020-03-10010 March 2020
Request for Additional Information - RR
ML19303D1662019-10-31031 October 2019
Requests for Additional Information for the Environmental Review of the Peach Bottom Subsequent License Renewal Application - Set 2 (EPID No. L-2018-RNW-0013)- RAIs
ML19232A1752019-08-20020 August 2019
Request for Additional Information - TSTF-500 Implementation LAR
ML19140A2832019-05-15015 May 2019
Email - Peach Bottom Atomic Power Station, Units 2 and 3 Second Round RAI Request - Set 1
ML19140A2822019-05-15015 May 2019
027 Pb FU RAI Subsequent to Clarification Call - Cu Greater than 15 Zn Holston (Jg)
ML19253D2932019-05-0707 May 2019
002 Attachment 4D Confirmation Water Chemistry Chereskin Revised (002)
ML19249C7252019-05-0303 May 2019
SLRA Requests for Additional Information - Set 2 May 3, 2019
ML19108A4282019-04-10010 April 2019
RAIs SLRA Set 1_ERO(Rev 1)
ML19079A0232019-03-19019 March 2019
Licensed Operator Positive Fitness-For-Duty Test
ML19058A2902019-02-27027 February 2019
Request for Additional Information - High Pressure Service Water One Time TS Change
ML19037A4832019-02-0606 February 2019
NRR E-mail Capture - Clarification Questions Associated with Staff Assessment of Peach Bottom Seismic Probabilistic Risk Assessment Report Dated August 28, 2018
ML19028A0062019-01-25025 January 2019
Secondary Containment LAR Requests for Additional Information
ML19017A0472019-01-16016 January 2019
Request for Additional Information - High Pressure Service Water One Time TS Change
ML18348B0292018-12-13013 December 2018
Subsequent License Renewal Severe Accident Mitigation Alternatives Requests for Additional Information
ML19010A3832018-12-0707 December 2018
Additional Documents Needed for Peach Bottom SLR Environmental Review
ML18324A6742018-11-15015 November 2018
Request for Additional Information (FINAL)- LAR to Allow 2SRV/SVs OOS at High Pressure
ML18312A4072018-11-0808 November 2018
Request for Additional Information (Public) - LAR to Allow 2SRV/SVs OOS at High Pressure
ML18276A0202018-10-0202 October 2018
NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Amendment Request to Revise Emergency Plan for Limerick and Peach Bottom
ML18240A1742018-08-28028 August 2018
Request for Additional Information (Final) - Adopt TSTF-500 Battery TS Changes LAR
ML18239A1322018-08-27027 August 2018
Request for Additional Information Final - Relief Request I5R-04
ML18228A6762018-08-14014 August 2018
Request for Additional Information - Adopt TSTF-500 Battery TS Changes LAR
ML18226A2012018-08-14014 August 2018
Request for Additional Information - Relief Request I5R-05
ML18214A2812018-08-0202 August 2018
Request for Additional Information Draft - Relief Request I5R-02
ML18200A2742018-07-17017 July 2018
Request for Additional Information 2nd Round (Final) - Adopt 50.69 License Amendment
ML18192A1192018-07-10010 July 2018
Request for Additional Information 2nd Round (Final) - Adopt 50.69 License Amendment
ML18178A4772018-06-27027 June 2018
Request for Additional Information 2nd Round - Adopt 50.69 License Amendment
ML18096B5062018-04-0606 April 2018
Request for Additional Information Exelon Generation Company, LLC Requested Amendment to Adopt 10 CFR 50.69 for Risk-informed Categorization and Treatment of Structures, Systems and Components
ML18094B0832018-04-0505 April 2018
Enclosurequest for Additional Information (Letter to P. Duke RAI Regarding Entergy Operations, Inc.'S Decommissioning Funding Plan Update for Salem and Hope Creek, and Peach Bottom ISFSIs Docket Nos. 72-48 and 72-29)
ML18067A1482018-03-0808 March 2018
Enclosurequest for Additional Information (Letter to P. R. Simpson Request for Additional Information Regarding Exelon Generating Company, Llc'S Decommissioning Funding Plan Update for Independent Spent Fuel Storage Installation)
ML17317B5502017-11-0909 November 2017
Licensed Operator Positive Fitness-For-Duty Test
ML17240A0062017-08-24024 August 2017
Request for Additional Information Regarding License Amendment Request for Measurement Uncertainty Recapture Power Uprate
2024-07-03
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August 22, 2012 MEMORANDUM TO: Meena K. Khanna, Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: Richard B. Ennis, Senior Project Manager /RA/ Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
SUBJECT:
PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3, DRAFT REQUEST FOR ADDITIONAL INFORMATION (TAC NOS. ME8535 AND ME8536)
The attached draft request for additional information (RAI) was transmitted on August 22, 2012, to Mr. Thomas Loomis of Exelon Generation Company, LLC (Exelon, the licensee). This information was transmitted to facilitate an upcoming conference call in order to clarify the
licensee=s amendment request for Peach Bottom Atomic Power Station (PBAPS), Units 2 and 3, dated April 27, 2012. The proposed amendment would: (1) adopt a new methodology for preparation of the reactor coolant system pressure-temperature (P-T) limits; (2) relocate the P-T limits in the technical specifications (TSs) to a new licensee-controlled document, the Pressure and Temperature Limits Report (PTLR); and (3) modify the TSs to add references to the PTLR. PBAPS, Units 2 and 3, are currently licensed to P-T limits that are applicable up to 32 effective full power years (EFPY). The PTLR would include P-T limits applicable to both 32 EFPY and 54 EFPY.
The draft RAI was sent to Exelon to ensure that the questions are understandable, the regulatory basis for the questions is clear, and to determine if the information was previously docketed. This memorandum and the attachment do not convey or represent an NRC staff position regarding the licensee's request.
Docket Nos. 50-277 and 50-278
Attachment:
Draft RAI
August 22, 2012 MEMORANDUM TO: Meena K. Khanna, Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: Richard B. Ennis, Senior Project Manager /RA/ Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
SUBJECT:
PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3, DRAFT REQUEST FOR ADDITIONAL INFORMATION (TAC NOS. ME8535 AND ME8536)
The attached draft request for additional information (RAI) was transmitted on August 22, 2012, to Mr. Thomas Loomis of Exelon Generation Company, LLC (Exelon, the licensee). This information was transmitted to facilitate an upcoming conference call in order to clarify the licensee=s amendment request for Peach Bottom Atomic Power Station (PBAPS), Units 2 and 3, dated April 27, 2012. The proposed amendment would: (1) adopt a new methodology for preparation of the reactor coolant system pressure-temperature (P-T) limits; (2) relocate the P-T limits in the technical specifications (TSs) to a new licensee-controlled document, the Pressure and Temperature Limits Report (PTLR); and (3) modify the TSs to add references to the PTLR.
PBAPS, Units 2 and 3, are currently licensed to P-T limits that are applicable up to 32 effective full power years (EFPY). The PTLR would include P-T limits applicable to both 32 EFPY and 54 EFPY. The draft RAI was sent to Exelon to ensure that the questions are understandable, the regulatory basis for the questions is clear, and to determine if the information was previously docketed. This memorandum and the attachment do not convey or represent an NRC staff position regarding the licensee's request.
Docket Nos. 50-277 and 50-278
Attachment:
Draft RAI
DISTRIBUTION PUBLIC DWidrevitz, NRR/EVIB LPL1-2 R/F BParks, NRR/SRXB RidsNrrDorlLpl1-2 Resource RidsNrrDorlDpr Resource RidsNrrPMPeachBottom Resource ACCESSION NO.: ML12236A154 OFFICE LPL1-2/PM NAME REnnis DATE 8/22/12 OFFICIAL RECORD COPY DRAFT REQUEST FOR ADDITIONAL INFORMATION REGARDING PROPOSED LICENSE AMENDMENT RELOCATION OF PRESSURE AND TEMPERATURE LIMIT CURVES TO THE PRESSURE AND TEMPERATURE LIMITS REPORT PEACH BOTTOM ATOMIC POWER STATION - UNITS 2 AND 3 DOCKET NOS. 50-277 AND 50-278 By letter to the Nuclear Regulatory Commission (NRC) dated April 27, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML121230354), Exelon Generation Company, LLC (Exelon, the licensee), submitted a license amendment request for Peach Bottom Atomic Power Station (PBAPS), Units 2 and 3. The proposed amendment would: (1) adopt a new methodology for preparation of the reactor coolant system pressure-temperature (P-T) limits; (2) relocate the P-T limits in the technical specifications (TSs) to a new licensee-controlled document, the Pressure and Temperature Limits Report (PTLR); and (3) modify the TSs to add references to the PTLR. PBAPS, Units 2 and 3, are currently licensed to P-T limits that are applicable up to 32 effective full power years (EFPY). The PTLR would include P-T limits applicable to both 32 EFPY and 54 EFPY.
The NRC staff has reviewed the information the licensee provided that supports the proposed amendment and would like to discuss the following issues to clarify the submittal.
- 1. Section 1.0 of Attachment 1 to the licensee's application dated April 27, 2012, states that relocation of the P-T limit curves to the PTLR is consistent with the guidance provided in NRC-approved GE Hitachi Nuclear Energy Licensing Topical Report NEDC-33178P-A, Revision 1 (ADAMS Accession No. ML092370486). Equations 4-2 and 4-3 in Section 4.3.2.1.1 of NEDC-33178P-A are used to determine if the generic Pressure Test - Non-Beltline, Curve A is applicable. The equations are as follows:
R / t 1/2 = 138 / 8 1/2 = 49 inch 1/2 Equation 4-2
R / t 1/2 Equation 4-3 As discussed in Section 4.3.2.1.1 of NEDC-33178P-A, if the plant-specific result of Equation 4-3 is greater than that of the generic value from Equation 4-2, the user is directed to perform a plant-specific evaluation. The NRC staff conducted the comparison and found that the PBAPS-provided geometry information results in a value greater than the generic value. Justify the use of the Section 4.3.2.1.1 curve or submit a plant-specific evaluation.
- 2. 10 CFR Part 50, Appendix G, Paragraph IV.A states that, "the pressure-retaining components of the reactor coolant pressure boundary [RCPB] that are made of ferritic materials must meet the requirements of the [American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code], supplemented by the additional requirements
Attachment set forth below." These requirements include paragraph IV.A.2, "Pressure-Temperature Limits and Minimum Temperature Requirements". Therefore, 10 CFR Part 50, Appendix G requires that P-T limits be developed for the ferritic materials in the reactor vessel (RV) beltline (neutron fluence 1 x 10 17 n/cm 2, E > 1 MeV), as well as ferritic materials not in the RV beltline (neutron fluence < 1 x 10 17 n/cm 2, E > 1 MeV). Further, 10 CFR Part 50, Appendix G requires that all RCPB components must meet the ASME Code,Section III requirements. The relevant ASME Code,Section III requirement that will affect the P-T limits is the lowest service temperature requirement for all RCPB components specified in Section III, NB-2332(b).
The P-T limit calculations for ferritic RCPB components that are not RV beltline shell materials may define P-T curves that are more limiting than those calculated for the RV beltline shell materials due to the following factors:
a) RV nozzles, penetrations, and other discontinuities have complex geometries that may exhibit significantly higher stresses than those for the RV beltline shell region. These higher stresses can potentially result in more restrictive P-T limits, even if the reference temperature (RT NDT) for these components is not as high as that of RV beltline shell materials that have simpler geometries.
b) Ferritic RCPB components that are not part of the RV may have initial RTNDT values, which may define a more restrictive lowest operating temperature in the P -T limits than those for the RV beltline shell materials.
Consequently, please describe how the P-T limit curves submitted for PBAPS, Units 2 and 3 and the methodology used to develop these curves, considered all RV materials (beltline and non-beltline) and the lowest service temperature of all ferritic RCPB materials, consistent with the requirements of 10 CFR Part 50, Appendix G.
